Forced convective boiling is of great interest for several applications in the power and process industry, particularly in nuclear plants. Under certain nominal, incidental or accidental conditions, a boiling crisis may occur resulting in the meltdown of the heating surface. It is then essential to predict as accurately as possible the thermal-hydraulic conditions leading to the occurrence of this boiling crisis. Such an objective cannot reasonably be achieved without a good description of the associated two-phase flow. The objective of the present study is twofold: (1) to identify the necessary key parameters for correctly describing boiling flows, and (2) to present in a didactic way an original stationary and local model involving these parameters. This new model is primarily based on four mixture balance equations, a submodel for the local vapor generation rate, and a turbulence submodel inspired by the pioneering work of [25]. The results obtained with this original boiling flow model are then compared to an extensive experimental data set obtained on a R12/R134a experimental facility. The comparison clearly demonstrates that this new model contains the fewer necessary submodels to describe the structure of a boiling two-phase flow under pressurized water reactor conditions. Subcooled boiling is acceptably described by the model. However, for higher values of void fraction, the model always predicts a nonexistent void fraction peak near the heating wall and overpredicts the wall and liquid temperatures. This behavior may be explained by: (i) the inadequacy of the radial turbulence modeling, (ii) the use of Prandtl's analogy whose validity under boiling conditions is questionable, and (iii) too simplistic a model for the vapor generation rate.

强制对流沸腾在电力和加工工业中的多种应用中具有重要意义，特别是在核电站中。在某些标称的、偶然的或偶然的情况下，可能会发生沸腾危机，导致加热面熔化。因此，必须尽可能准确地预测导致这种沸腾危机发生的热工水力条件。如果没有对相关两相流的良好描述，就无法合理地实现这样的目标。本研究的目标是双重的：（1）确定正确描述沸腾流动所需的关键参数，以及（2）以教学的方式呈现包含这些参数的原始静态和局部模型。这个新模型主要基于四个混合平衡方程，局部蒸汽生成率的子模型，以及受 [25] 开创性工作启发的湍流子模型。然后将使用该原始沸腾流动模型获得的结果与在 R12/R134a 实验设备上获得的大量实验数据集进行比较。比较清楚地表明，这个新模型包含较少的必要子模型来描述压水反应堆条件下沸腾两相流的结构。该模型可以接受过冷沸腾。然而，对于较高的空隙率值，模型总是预测加热壁附近不存在的空隙率峰值，并高估了壁温和液体温度。这种行为可以解释为：（i）径向湍流建模的不足，（ii）使用 Prandtl'